Application of CFD for nuclear reactor safety analyses

Transcription

1 Application of CFD for nuclear reactor safety analyses Bogdán Yamaji assistant researcher Institute of Nuclear Techniques Budapest University of Technology and Economics June nd Consultancy Meeting of INPRO COOL Project 1

2 Wide spectrum of CFD research CFD projects GenII+III and training reactor: Coolant mixing in the fuel assembly : in the rod bundle and assembly head VVER-440 Subchannel calculations for VVER-440 fuel assembly Coolant mixing in RPV - VVER-440 Coolant mixing in RPV - VVER-1000 Mixing processes in the cooling pond Thermal-hydraulic processes in the Training Reactor Coolant mixing in the fuel assembly EK-10 (BME Training Reactor) One-phase CFD analyses of the serious incident occurred in Paks-2, 2003: course of the incident, post-incident state of the system, calculations backing the recovery work June nd Consultancy Meeting of INPRO COOL Project 2

3 Wide spectrum of CFD research CFD projects GenIV and fusion: CFD validation with measurements of supercritical water Mixing and thermal-hydraulics in HPLWR fuel assembly CFD modelling of annular flow of lead-bismuth eutectic along heated rod measurement data from FZK test facility CFD analyses of molten salt reactors ITER related CFD research HCPB Test Blanket Module analyses: TBM stiffening grids, manifold, breeding unit, cap, first wall HETRA experimental facility design and analysis GRICAMAN experimental facility design Codes: ANSYS CFX (v.11, 12), ICEM CFD, Workbench (OpenFOAM - open source) June nd Consultancy Meeting of INPRO COOL Project 3

4 VVER-440/213 detailed model elements June nd Consultancy Meeting of INPRO COOL Project 4

5 VVER-440/213 mixing factors at the core inlet June nd Consultancy Meeting of INPRO COOL Project 5 * Flomix_D11_WP4_Finalreport * * * * * *

6 VVER-1000 mixing in RPV OECD/NEA benchmark: coolant mixing in RPV and temperature distribution at the core inlet measurement data: Kozloduy NPP June nd Consultancy Meeting of INPRO COOL Project 6

7 measurement VVER-1000 mixing in RPV difference delta T i calc, i T calc, i T max T T [ K ] T data, 13 K data, i i min [ K ] June nd Consultancy Meeting of INPRO COOL Project 7

8 Training reactor fuel TH EK-10 EK10 - BME Training Reactor fuel assembly Coupled kinetics analysis of power transients Model length (Z direction) Fuel length Width in X and Y direction Fuel cladding outer diameter Fuel cladding inner diameter 540 mm 500 mm 32,5 mm 10 mm 7 mm June nd Consultancy Meeting of INPRO COOL Project 8

9 VVER-440 fuel assembly Assembly head Fuel bundle Sub-channel Analysis of mixing in the head and the bundle Verification of sub-channel codes Analysis of new fuel assembly types Validated against measurements of Kurchatov Insititute June nd Consultancy Meeting of INPRO COOL Project 9

10 VVER-440 fuel assembly sub-channel calculations M1 M2 M3 M4 M5 M v Experiment M1 M2 M3 M4 M5 M y* Detailed analysis: mesh, turbulence modelling Measurement data: Trupp and Azard,1975 v June nd Consultancy Meeting of INPRO COOL Project Experiment BSL Reynolds Stress SSG Reynolds Stress SST k-epsilon y*

11 VVER-440 fuel assembly bundle calculations Convective mixing between sub-channels Detailed analysis of spacing grids June nd Consultancy Meeting of INPRO COOL Project 11

12 Supercritical water CFX validation against three measurements 3D CFX models, different turbulence modelling measurement data by Swenson, Herkenrath, Yamagata Model development for supercritical water behaviour S1: (T in <T pc ;T in =390,85 C) S2: (T in >T pc ;T in =408 C) June nd Consultancy Meeting of INPRO COOL Project 12

13 Supercritical water - HPLWR HPLWR (High Performance Light Water Reactor) fuel bundle Steady state CFX calculations of ¼ HPLWR fuel bundle model helical spacers (Co-operation with IKE, University of Stuttgart) Flow direction June nd Consultancy Meeting of INPRO COOL Project 13

14 Annular Flow of LBE along a Heated Rod Annular flow of lead-bismuth eutectic along a heated rod Validation of CFD models and measurements of heated Rod case by Forschungszentrum Karlsruhe (FZK) Different computational meshes Analysis of turbulence modelling June nd Consultancy Meeting of INPRO COOL Project 14

15 June nd Consultancy Meeting of INPRO COOL Project 15

16 MOSART CFD analyses of molten salt reactors MSRE MOST June nd Consultancy Meeting of INPRO COOL Project 16

17 ITER ITER Helium Cooled Pebble Bed Test Blanket Module June nd Consultancy Meeting of INPRO COOL Project 17

18 Stiffening grid ITER TBM Manifold Caps Breeding unit June nd Consultancy Meeting of INPRO COOL Project 18

19 Application of PIV/LIF Small-scale experimental facility for validation of CFD calculations Coolant mixing and thermal stratification System components: PIV Particle Image Velocimetry LIF Laser Induced Fuorescece Seeding particles for PIV, fluorescent dye for LIF 135 mj, 532 nm Nd-YAG dual laser (15 Hz) 2x(1600*1200) pixel digital camera (30 fps) Software (Dynamic Studio) thermocouples, flow meters, etc small plexiglas rectangular vessel ( aquarium ) engineering equipments (heaters, valves, pumps) June nd Consultancy Meeting of INPRO COOL Project 19

20 Application of PIV/LIF June nd Consultancy Meeting of INPRO COOL Project 20

21 Application of PIV/LIF June nd Consultancy Meeting of INPRO COOL Project 21

22 Application of PIV/LIF June nd Consultancy Meeting of INPRO COOL Project 22

23 Application of PIV/LIF Measurement of concentration/temperature C=0 C= June nd Consultancy Meeting of INPRO COOL Project 23

24 Application of PIV/LIF June nd Consultancy Meeting of INPRO COOL Project 24

25 Core and irradiating facilities BME Training Reactor 100 kw, pool type Irradiation channels, irradiation tunnel, pneumatic rabbit system